【摘要】：針對(duì)核電廠一回路系統(tǒng)管道內(nèi)壁沉積的腐蝕活化產(chǎn)物,開展γ輻射源項(xiàng)就地測(cè)量技術(shù)研究�；诟呒冩N探測(cè)器開發(fā)了輻射源項(xiàng)就地測(cè)量系統(tǒng)(Sterm-HPGe),利用蒙特卡羅軟件進(jìn)行了無源效率刻度,并開展了實(shí)驗(yàn)室效率驗(yàn)證工作。在300~1 408 ke V能量范圍內(nèi),HPGe探測(cè)器在無準(zhǔn)直器屏蔽和有準(zhǔn)直器屏蔽情況下,點(diǎn)源全能峰效率計(jì)算值與測(cè)量值的相對(duì)偏差分別在±5%和±10%以內(nèi)。測(cè)量系統(tǒng)在我國壓水堆核電廠進(jìn)行了現(xiàn)場(chǎng)應(yīng)用,能夠較準(zhǔn)確地測(cè)量出管道內(nèi)60Co、58Co、110mAg等典型沉積核素的源項(xiàng)活度,管道表面劑量率的計(jì)算值與測(cè)量值的相對(duì)偏差一般在±40%以內(nèi)。
[Abstract]:The in-situ measurement of 緯 -radiation source term was carried out for the corrosion activated products of pipeline inner wall deposition in primary circuit system of nuclear power plant. Based on the high purity germanium detector, a radiation source in-situ measurement system (Sterm-HPGe) was developed. The passive efficiency calibration was carried out by Monte Carlo software, and the laboratory efficiency verification was carried out. In the energy range of 1 408ke V, the relative deviation between the calculated peak efficiency of point source and the measured value is within 鹵5% and 鹵10%, respectively, in the case of no collimator shielding and collimator shielding. The measurement system has been applied in the field of PWR nuclear power plant in China. It can accurately measure the source activity of typical deposited nuclides such as 60CoN58CoHN 110mAg in the pipeline. The relative deviation between the calculated value of the surface dose rate of the pipeline and the measured value is generally within 鹵40%.
【作者單位】： 中國輻射防護(hù)研究院;中國原子能科學(xué)研究院;
【分類號(hào)】：R144

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